"Sodium Fast Reactors" trang 1 - tải miễn phí từ tailieuXANH
Semiempirical model for wet scrubbing of bubble rising in liquid pool of sodium-cooled fast reactor

Semiempirical model for wet scrubbing of bubble rising in liquid pool of sodium-cooled fast reactor
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Safety aspects of intermediate heat transport and decay heat removal systems of sodium cooled fast reactors

Safety aspects of intermediate heat transport and decay heat removal systems of sodium cooled fast reactors
7    41    0
Numerical approach for quantification of selfwastage phenomena in sodium cooled fast reactor

Numerical approach for quantification of selfwastage phenomena in sodium cooled fast reactor
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Numerical investigation on vortex behavior in wire-wrapped fuel assembly for a sodium fast reactor

Numerical investigation on vortex behavior in wire-wrapped fuel assembly for a sodium fast reactor
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Influence of design modification of control rod assembly for Prototype Generation IV Sodium-cooled Fast Reactor on drop performance

Influence of design modification of control rod assembly for Prototype Generation IV Sodium-cooled Fast Reactor on drop performance
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Metal fuel development and verification for prototype generation IV sodium-cooled fast reactor

Metal fuel development and verification for prototype generation IV sodium-cooled fast reactor
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Nuclear engineering and technology, Overall system description and safety characteristics of prototype gen iv sodium cooled fast reactor in Korea

Nuclear engineering and technology, Overall system description and safety characteristics of prototype gen iv sodium cooled fast reactor in Korea
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CADOR “Core with Adding DOppleR effect” concept application to sodium fast reactors

CADOR “Core with Adding DOppleR effect” concept application to sodium fast reactors
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Modeling of hydrodynamic processes at a large leak of water into sodium in the fast reactor coolant circuit

Modeling of hydrodynamic processes at a large leak of water into sodium in the fast reactor coolant circuit
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Evaluation of cobalt free coatings as hardfacing material candidates in sodium-cooled fast reactor and effect of oxygen in sodium on the tribological behaviour

Evaluation of cobalt free coatings as hardfacing material candidates in sodium-cooled fast reactor and effect of oxygen in sodium on the tribological behaviour
11    46    0
Pumps modelling of a sodium fast reactor design and analysis of hydrodynamic behavior

Pumps modelling of a sodium fast reactor design and analysis of hydrodynamic behavior
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Numerical investigation of fluid – structure interaction (FSI) on sodium leakage accident at prototype fast breeder reactor monju

Numerical investigation of fluid – structure interaction (FSI) on sodium leakage accident at prototype fast breeder reactor monju
11    56    2
On the Particle Swarm Optimization of cask shielding design for a prototype Sodium-cooled Fast Reactor

On the Particle Swarm Optimization of cask shielding design for a prototype Sodium-cooled Fast Reactor
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Drop performance test of conceptually designed control rod assembly for prototype generation iv sodium cooled fast reactor

Drop performance test of conceptually designed control rod assembly for prototype generation iv sodium cooled fast reactor
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On the safety and performance demonstration tests of prototype Gen-IV sodium cooled fast reactor and validation and verification of computational codes

On the safety and performance demonstration tests of prototype Gen-IV sodium cooled fast reactor and validation and verification of computational codes
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The investigation of burnup characteristics using the serpent monte carlo code for a sodium cooled fast reactor

The investigation of burnup characteristics using the serpent monte carlo code for a sodium cooled fast reactor
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Evolution of the collective radiation dose of nuclear reactors from the 2nd through to the 3rd generation and 4th generation sodium-cooled fast reactors

Evolution of the collective radiation dose of nuclear reactors from the 2nd through to the 3rd generation and 4th generation sodium-cooled fast reactors
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Nuclear transmutation of long-lived fission product I-129 in radial blanket of sodium-cooled fast reactor

Nuclear transmutation of long-lived fission product I-129 in radial blanket of sodium-cooled fast reactor
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Detailed neutronic study of the power evolution for the European Sodium Fast Reactor during a positive insertion of reactivity

Detailed neutronic study of the power evolution for the European Sodium Fast Reactor during a positive insertion of reactivity
9    13    1
Multi-physics models for design basis accident analysis of sodium fast reactors. Part I: Validation of three-dimensional TRACE thermal-hydraulics model using Phenix end-of-life experiments

Multi-physics models for design basis accident analysis of sodium fast reactors. Part I: Validation of three-dimensional TRACE thermal-hydraulics model using Phenix end-of-life experiments
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